Education background

2020.03-2021.10 Dr.-Ing., Karlsruhe Institute of Technology (KIT), Germany

2015.09-2020.03 Master-PhD program, Shanghai Jiao Tong University (SJTU), China

2011.09-2015.06 B.Sc., Xi’an Jiaotong University (XJTU), China

Work experience

2022.06-Present College of Smart Energy, Shanghai Jiao Tong University (SJTU), China

Innovative nuclear power system

Digital twin

Uncertainty analysis

[1] Song, H.D., Liu, X.J., Song, M.Q., 2023. Comparative study of data-driven and model-driven approaches in prediction of nuclear power plants operating parameters. Applied Energy, 341: 121077.

[2]Song, M.Q., Liu, X.J., Cheng, X., 2023. Modelling and experimental validation of heat transfer behavior during trans-critical transients. Annals of Nuclear Energy, 186: 109771.

[3]Song, H., Song, M.Q. Liu, X., 2022. Online autonomous calibration of 

digital twins using machine learning with application to nuclear power plants. Applied Energy, 326: 119995.

[4] Song, M.Q., Liu, X.J., Cheng, X., 2022. A new correlation for post-dryout heat transfer in upward vertical flow. Nuclear Engineering and Design, 392: 111747.

[5]Song, M.Q., Liu, X.J., Cheng, X., 2021. Prediction of critical heat flux (CHF) for the high-pressure region in uniformly heated vertical round tubes. Annals of Nuclear Energy, 158: 108303. 

[6] Song, M.Q., Liu, X.J., 2021. Assessment of CHF and post-CHF Heat Transfer Models for High-Pressure Condition. Frontiers in Energy Research, 9: 782086. 

[7]Song, M.Q., Zhang, Q.M., Guo, Y.H., et al., 2016. Numerical modeling of thermal loading of diamond crystal in X-ray FEL oscillators. Chinese Physics C, 40 (4): 048101. 

[8] Liu, X.J., Song, M.Q., Cheng, X., 2019. Current status and challenges of supercritical fluid thermal hydraulics. Nuclear Engineering and Design,354: 110176. 

Modeling of post-dryout heat transfer and rewetting at fuel rods under BWR and PWR relevant conditions (MOPOW II Project) , BMWi

Improvement of the heat transfer modeling in ATHLET for safety analysis of Supercritical Water-Cooled Reactor(VERA Project), BMWi

Research and modeling of supercritical forced convective heat transfer, STCSM

ISSNP-2016：Best Student Papers Award

16^th Annual Meeting on Nuclear Thermal-Hydraulic Conference：Best Papers Awards